ML20080S617

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Describes Results of Main Turbine Bypass Sys Testing Performed to Determine Position Vs Flow Relationship for Main Turbine Bypass Valves,Per Tech Spec 3/4.7.10
ML20080S617
Person / Time
Site: LaSalle 
Issue date: 10/13/1983
From: Schroeder C
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
7453N, NUDOCS 8310180425
Download: ML20080S617 (2)


Text

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/ Chicago Illinois 60690 October 13, 1983 Mr. Harold R.

Denton, Director Office of Nuclear Reactor Regulation

-U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Bypass Valve Position / Flow Determination NRC Docket No. 50-373

Reference:

(a)

Technical Specification 3/4.7,10, Main Turbine Bypass System

Dear Mr. Denton:

As required by Reference (a),

testing has been performed to determine the position versus flow relationship for the main turbine bypass valves.

This letter is to inform you of the results of these tests gs specified in the footnote of the referenced Technical Specification.

The test data obtained per STP-26 shows that the 80% of rated flow condition specified in the Technical Specification occurs at a total bypass valve position of 89%.

Because previous response time tests have shown that the 100%

stroke time of the bypass valves is within the 200 milliseconds allowed by the Technical Specification, the station response time testing procedures have been conservatively written to compare the 100% stroke time to the criteria rather than the 89% stroke time.

However, the option to use the 89% stroke time will be kept open in case it is needed in the future.

Also, it should be noted that a change will be submitted for the Unit 1 Technical Specification 3/4.7.10 to make its wording consistent with the Unit 2 Specification and the Standard Technical Specifications.

The new wording for Specification 4.7.10.b.3 will be:

" Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIME to be less than or equal to 200 milliseconos."

To the cest of my knowledge and belief the statements contained herein are true and correct.

In some respects these statements are not based on my personal knowledge but upon information furnished by other Commonwealth Edison employees.

Such information has been reviewed in accordance with Company practice and I believe it to be reliable.

P 8310180425 831013 PDR ADOCK 05000373

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'. s J Enclosed for your use please find one signed original and forty (40) copies of this letter.

If'there are any further questions in this matter, pelase contact this office.

Very truly yours, k

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W. Schroeder Nuclear Licensing Administrator 4

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NRC Resident Inspector (LSCS) f bg i

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